Preliminary study on alternative magnetic layout (AML) for tokamaks reactors in the TRUST project framework

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
S. Carusotti , R. Lombroni , M. Scarpari , M. Notazio , A. Pizzuto , F. Crisanti , P. Fanelli , G. Calabrò
{"title":"Preliminary study on alternative magnetic layout (AML) for tokamaks reactors in the TRUST project framework","authors":"S. Carusotti ,&nbsp;R. Lombroni ,&nbsp;M. Scarpari ,&nbsp;M. Notazio ,&nbsp;A. Pizzuto ,&nbsp;F. Crisanti ,&nbsp;P. Fanelli ,&nbsp;G. Calabrò","doi":"10.1016/j.fusengdes.2025.115246","DOIUrl":null,"url":null,"abstract":"<div><div>The main aim of this study is to explore a conceptual Alternative Magnetic Layout (AML) for the future nuclear fusion reactor based on the Tokamak concept. The proposed concept is eventually applied as a large down scaled study for the new academic tokamak Tuscia Research University Small Tokamak (TRUST), under construction at University of Tuscia (UNITUS). In this proposal the Central Solenoid (CS) placed around the Toroidal Field (TF) coils providing a relevant reduction in the reactor radial build. In order to compensate the increase of the toroidal filed on the coils, that it is intrinsic in such proposal, High Temperature Superconductor (HTS) material is foreseen for the TF coils. An overview of the proposed design and a possible plasma scenario is presented showing the AML advantages and disadvantages. The electromagnetic and structural characterizations for a preliminary design of the TF coils system is included in this paper to prove the engineering feasibility of the solution. Moreover, the involvement of the AML design in the TRUST project framework is presented. TRUST is a flexible and low-cost university-class experiment, to train the next generation of fusion engineers and physicists. Beyond its academic goal, TRUST is designed to allow easy replacement of the plasma facing components and testing innovative technologies (i.e., meta-materials) and materials including a feasible upgrade the magnetic system from copper to HTS.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"219 ","pages":"Article 115246"},"PeriodicalIF":1.9000,"publicationDate":"2025-06-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625004429","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0

Abstract

The main aim of this study is to explore a conceptual Alternative Magnetic Layout (AML) for the future nuclear fusion reactor based on the Tokamak concept. The proposed concept is eventually applied as a large down scaled study for the new academic tokamak Tuscia Research University Small Tokamak (TRUST), under construction at University of Tuscia (UNITUS). In this proposal the Central Solenoid (CS) placed around the Toroidal Field (TF) coils providing a relevant reduction in the reactor radial build. In order to compensate the increase of the toroidal filed on the coils, that it is intrinsic in such proposal, High Temperature Superconductor (HTS) material is foreseen for the TF coils. An overview of the proposed design and a possible plasma scenario is presented showing the AML advantages and disadvantages. The electromagnetic and structural characterizations for a preliminary design of the TF coils system is included in this paper to prove the engineering feasibility of the solution. Moreover, the involvement of the AML design in the TRUST project framework is presented. TRUST is a flexible and low-cost university-class experiment, to train the next generation of fusion engineers and physicists. Beyond its academic goal, TRUST is designed to allow easy replacement of the plasma facing components and testing innovative technologies (i.e., meta-materials) and materials including a feasible upgrade the magnetic system from copper to HTS.
TRUST项目框架下托卡马克堆备选磁布局(AML)的初步研究
本研究的主要目的是探索基于托卡马克概念的未来核聚变反应堆的概念性替代磁布局(AML)。所提出的概念最终被应用于图西亚研究大学(UNITUS)正在建设的新学术托卡马克小型托卡马克(TRUST)的大规模研究。在这个建议中,中央螺线管(CS)放置在环形场(TF)线圈周围,提供了相应的反应堆径向构建减少。为了补偿这种方案中固有的线圈上环向磁场的增加,设想在TF线圈上使用高温超导体(HTS)材料。概述了提出的设计和可能的等离子体场景,展示了AML的优点和缺点。本文给出了TF线圈系统初步设计的电磁特性和结构特性,以证明该方案在工程上的可行性。此外,还介绍了AML设计在TRUST项目框架中的作用。TRUST是一项灵活、低成本的大学级实验,旨在培养下一代聚变工程师和物理学家。除了其学术目标之外,TRUST的设计还允许轻松更换面向等离子体的组件,并测试创新技术(即超材料)和材料,包括将磁性系统从铜升级到高温超导。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
求助全文
约1分钟内获得全文 求助全文
来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:604180095
Book学术官方微信